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Journal Metrics

Source Normalized Impact per Paper (SNIP): 1.403ℹSource Normalized Impact per Paper (SNIP):2014: 1.403SNIP measures contextual citation impact by weighting citations based on the total number of citations in a subject field.

SCImago Journal Rank (SJR): 0.986ℹ

SCImago Journal Rank (SJR):2014: 0.986SJR is a prestige metric based on the idea that not all citations are the same. SJR uses a similar algorithm as the Google page rank; it provides a quantitative and a qualitative measure of the journal’s impact.

Siting a nuclear geological repository entails high economic, social, and political costs. The concept of expanding the capacity of repository is of great interest to the nuclear industry. Partitioning...

The addition of some materials with various fractions in the composition of concrete has provided concrete forms more efficient for gamma ray shielding when compared to ordinary concrete. Selected materials...

Mixing and thermal stratification often occur in passive containment cooling systems. Currently, most of reactor system analysis codes do not use the thermal stratification to simplify the calculation....

In this paper, effect of the spallation target neutronic parameters such as beam profile, proton beam energy (Ep), target thicknesses and for different materials in an Accelerator Driven Subcritical...

Several 2D cell and 3D supercell models for reactivity device simulation have been proposed along the years for CANDU-6 reactors to generate 2-group cross section databases for finite core calculations...

We study the stationary nuclear fission wave (NFW) in the CANDLE fission wave reactor analytically and numerically. The focus of this work is to elucidate in a universally applicable way the variation...

Given postulated accidents that go beyond the plant design basis, long term passive cooling for the nuclear reactor spent fuel pool is important to demonstrate. Large amount of heat transport with small...

A mathematical separated flow model has been developed that is applicable to the annular two-phase flow in the rectangular narrow channels with peripheral heating. The theoretical annular flow model...

Atucha-2 is a Siemens-designed pressurized heavy water reactor in the Republic of Argentina. The correct prediction of the negative reactivity introduced in the moderator by an Emergency Boron Shutdown...

We studied neutron power instability in BWRs of four different nuclear power plants (NPP). The methodology applied in this study is a properly structured, coherent and expanded use of conventional techniques...

China Lead-based Research Reactor (CLEAR-I) will be built to develop the technologies of lead–bismuth eutectic cooled reactor. The In-Vessel Fuel Handling System (IVFHS) can achieve all positional refueling...

The Purdue NMR (Novel Modular Reactor) represents a BWR-type small modular reactor with a significantly reduced reactor pressure vessel (RPV) height. Specifically, it has one third the height of a conventional...

In this paper, the multi-point dynamics code BELLA and its benchmarking with respect to SAS4A/SASSYS-1 is described for a small fast reactor cooled with natural convection of lead (ELECTRA). It is shown...

In a periodic pulsed reactor, the reactor state varies periodically from slightly subcritical to slightly prompt supercritical for producing periodic power pulses. Such periodic state change is accomplished...

In this work, the implementation of a collision history-based approach to sensitivity/perturbation calculations in the Monte Carlo code SERPENT is discussed. The proposed methods allow the calculation...

A reliable estimation on the likelihood of human error is very critical for evaluating the safety of a large process control system such as NPPs (Nuclear Power Plants). In this regard, one of the determinants...

The self powered neutron detectors (SPNDs) play an important role in nuclear reactor monitoring. The 3-D power distribution and parameters used to evaluate the operation condition of reactor and the...

Core degradation evaluation of probability, progression and consequences of a core degradation accident is critical for evaluation of risk as well as its mitigation. However, research and modeling of...

In heterogeneous BN models, the interplay between symmetries leaving the material distribution invariant and the direction of the buckling vector is of key importance. A sufficient condition for the...

Personnel radiation safety is one of the most important issues during the dismantling of nuclear installations. In this paper, results of modeling radiation doses during the dismantling of the large...

Severe Accident Management Guidelines (SAMGs) suggests mitigating the consequence of severe accident scenarios by using the non-safety systems if the safety systems are unavailable. For 1000MWe advanced...

A new approach for passive acoustic leak detection in sodium fast reactors without using a priori knowledge on the leak noise is introduced. The new approach is tested on recordings of argon and water...

The control rods (CRs) worth is key parameter for the research reactors (RRs) operation and utilization. Control rods worth computation is a challenge for the full deterministic calculation methodology,...

The primary objective of this work is to find design approaches that will enable 3D fuel shuffling in stationary breed-and-burn (B&B) cores and to quantify the attainable reduction in peak DPA and change...

The treatment of low probability events leading to core disruption is one of the key issues of R&D plans for the advanced reactor systems in general, and for sodium fast reactors in particular. Regarding...

In the present study, we develop a Steam-generator Thermohydraulics Analysis code based on Fluent (STAF) for predicting the three-dimensional localized thermal–hydraulic characteristics in the primary...

Recently a conceptual structure design of helium-cooled solid breeder blanket was proposed as one of the candidates for the Chinese Fusion Engineering Test Reactor (CFETR). In the blanket, a trapezoidal...

The analysis of neutron kinetics relies on the knowledge of adjoint-weighted kinetics parameters, which are key to safety issues in the context of transient or accidental reactor behavior. The Iterated...

A module based optimization method using genetic algorithms (GA), and multivariate regression analysis has been developed to optimize a set of parameters in the design of a nuclear reactor. GA simulates...

After the Fukushima accident, a couple of novel issues have raised in terms of the safety assessment of nuclear power plants (NPPs). This means that the performance of human operators should be properly...

Water seal formation in the loop seal in pressurized water reactors can occur during a small or intermediate break loss-of-coolant accident, causing temporary fuel overheating. Quantification of the...

In this paper, two small ultra-long-life lead-bismuth-cooled cores having 48 and 58 effective full power years (EFPYs) of operation life are neutronically designed, and their core physics characteristics...

To judge the applicability of a critical experiment, it is necessary to confirm the similarities of the experiment with actual reactor conditions or equipment. The concept of the “representativity factor”...

This paper describes an approach for coupled-code multiphysics reactor core simulations that is being developed by the Virtual Environment for Reactor Applications (VERA) project in the Consortium for...

One of the most intensively developing areas in the LWR multi-physics is a coupling of different best estimate 3-D neutron kinetic (BIPR, DYN3D, KIKO3D, NEM, PARCS, etc.) and thermal hydraulic (ATHLET,...

Since some years, there is a worldwide trend to move towards “higher-fidelity” simulation techniques in reactor analysis. One of the main objectives of the research in this area is to enhance the prediction...

The development of multi-physics multi-scale coupled methodologies for Light Water Reactor (LWR) analysis requires comprehensive validation and verification procedures, which include well-established...

This article presents the implementation of a coupling between the 3D neutron kinetic core model DYN3D and the commercial, general purpose computational fluid dynamics (CFD) software ANSYS-CFX. In the...

The Monte Carlo method provides the most accurate description of the particle transport problem. The criticality problem is simulated by following the histories of individual particles without approximating...

The advanced numerical simulation of a realistic physical system typically involves multi-physics problem. For example, analysis of a LWR core involves the intricate simulation of neutron production...

A need exists in the nuclear industry for higher-fidelity tools for light water reactor (LWR) analysis, due to increasing core heterogeneity and higher burnup of fuels. In order to address this need,...

In this paper we present a fine-mesh solver aimed at resolving in a coupled manner and at the pin cell level the neutronic and thermal-hydraulic fields. Presently, the tool considers Pressurized Water...